ML20149L492

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Notice of Violation from Insp on 951217-960127.Violation Noted:Inadequate Design Control Measures Applied to Plant Design Changes Affected Amount of Trisodium Phosphate Needed to Meet Postaccident Containment Sump Water Design Basis
ML20149L492
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/22/1996
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20149L486 List:
References
50-285-95-24, NUDOCS 9602260380
Download: ML20149L492 (2)


Text

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ENCLOSURE 1 NOTICE OF VIOLATION Omaha Public Power District Docket:

50-285 Fort Calhoun Station License:

DPR-40 During an NRC inspection conducted on December 17, 1995, through January 27, 1996, two violations of NRC requirements were identified.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,"

(60 FR 34381; June 30, 1995), the violations are listed below:

A.

Appendix B of 10 CFR Part 50, Criterion III, states, in part, that design control measures shall be established to assure that applicable regulatory requirements and a design basis as defined in 50.2 and as specified in the license application, for those structures, systems, and components to which this appendix applies, are correctly translated into specifications, drawings, procedures, and instructions.

These measures shall also be applied to design changes.

Contrary to the above, inadequate design control measures were applied to plant design changes that affected the amount of trisodium phosphate needed to meet the postaccident containment sump water design basis of a pH greater than 7.

On December 4, 1995, the quantity of trisodium phosphate maintained inside containment to neutralize the postaccident containment sump water to a pH of 7 was found to have been inadequate at times during operation.

Changes in reactor coolant system maximum boron concentration were not adequately incorporated into calculation of the amount of trisodium phosphate required to satisfy the design basis.

This is a Severity Level IV violation (285/9524-02) (Supplement I).

B.

Technical Specification 5.8.1 states, in part, that written procedures and administrative policies shall be established, implemented, and maintained that meet or exceed the minimum requirements of Regulatory Guide 1.33.

Regulatory Guide 1.33, Appendix A, Section 9.a, states, in part, that maintenance that can affect the performance of safety-related equipment shall be performed in accordance with written procedures or documented instructions appropriate to the circumstances.

Maintenance Procedure PE-RR-CCW-0100, Step 6.14.1, directs operations to open the inlet component cooling water valve for the heat exchanger being tested.

Contrary to the above, operations opened the component cooling water inlet valve and outlet valve, allowing component cooling water flow to be diverted away from the other heat exchangers in service.

This is a Severity Level IV violation (285/9524-01) (Supplement I).

9602260380 960222 PDR ADOCK 05000285 G

PDR

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D

e Pursuant to the provisions of 10 CFR 2.201, Omaha Public Power District is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).

This reply should be clearly marked as a " Reply to a hotice of Violation" and should include for each violation:

(1) the reason for the violation or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.

Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.

If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why t e license should not be modified, suspended, or revoked or why h

such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

Because the response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.

However, if it is necessary to include such information, it should clearly indicate the specific information that should not be placed in the PDR and provide the legal basis to support the request for withholding the information from the public.

Dated at Arlington, Texas this 22nd day of February 1996 l

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